ML042250444

Administrative Jpms for D. C. Cook Retake Examination - August 2004

ML042250444
Person / Time
Site:	Cook
Issue date:	08/10/2004
From:	Mcneil D NRC/RGN-III/DRS/OLB
To:	American Electric Power Co
References
50-315/04-302, 50-316/04-302 50-315/04-302, 50-316/04-302
Download: ML042250444 (8)

Text

NRC2004-A2a Revision: 0

Title:

Determine Applicable Technical Specifications and Initiate Prompt NRC Notification.

REFERENCES:

Technical Specification Section 2.0 Safety Limits and Limiting Safety System Settings Technical Specification Section 6.7 Safety Limit Violation PMP-7030-001-001, Prompt NRC Notification Task: Verify applicable Tech Spec actions are taken K/A: 2.1.33 Ability to recognize indications for system operating parameters which are entry-level conditions for technical specifications.

K/A IMPORTANCE: SRO 4.0 RO 3.4 EVALUATION SETTING Classroom or Office HANDOUTS Task Briefing Sheet ATTACHMENTS None SIMULATOR SETUP None

NRC2004-A2a Revision: 0

Title:

Determine Applicable Technical Specifications and Initiate Prompt NRC Notification.

Task Objectives/Standards In accordance with the plants Technical Specifications determine the applicable action statements that must be entered and all of the required actions associated with the action statement.

Task Briefing You are an extra SRO.

Unit 2 was at 100% reactor power when a plant transient occurred fifteen minutes ago which caused RCS pressure to increase to 2856 psig. The Crew is responding to the emergency.

RCS pressure is currently stable at 2235 psig and all safety systems functioned as designed.

The Shift Manager has directed you to refer to the Technical Specifications and determine all of the applicable sections that apply and the required actions that must be taken to comply with the Technical Specifications. Complete the required documentation and inform the Shift Manager of required actions and notifications.

Note Simulator Indications are NOT applicable to this JPM

NRC2004-A2a Revision: 0

Title:

Determine Applicable Technical Specifications and Initiate Prompt NRC Notification.

Acceptance Criteria Shift Manager informed that the requirements from Section 2 and from Section 6 of the Technical Specifications must be met. Form PMP7030-001-001, Prompt NRC Notification, NRC form 361 must be completed.

Action:

CT Informs shift manager that Technical Specification 2.1.2 applies. The Reactor Coolant System pressure shall not exceed 2735 psig. "Whenever the Reactor Coolant System pressure has exceeded 2735 psig be in HOT STANDBY with the Reactor Coolant System pressure within limits within 1 Hour."

CT Informs shift manager that Technical Specification 6.7.1 applies. Informs Shift Manger that the NRC Operations Center shall be notified by telephone as soon as possible and in all cases within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, that the Chairman of the NSDRC shall be notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, that a Safety Limit Violation Report shall be prepared.

CT Applicant retrieves PMP-7030-001-001, Rev. 7, Page 24, "Prompt NRC Notification."

1. Enters the following in the applicable boxes:

current time for "Notification Time,"

DC Cook for "Facility or Organization,"

2 for "Unit,"

own name for "Name of Caller,"

Station phone number for "Call Back #,"

current time minus 15 minutes & eastern time zone for "Event Time &

Zone" August 10, 2004 for "Event Date,"

100%, Mode 1 for "Power/Mode Before," and 0%, Mode 3 for "Power/Mode After."

CT 2. Checks block for 50.72 Non-Emergency Block.

CT 3. Checks block for 1-Hr Non-Emergency 10 CFR 50.72(b)(1).

4 Checks block for 4-Hr Non-Emergency RPS Actuation (scram)

CT 5. Enters a description of the event in "Description."

6. Checks block that NRC Resident is to be notified.

7. Fills in the remainder of page - non-critical. No material should be entered on back of form.

END of JPM.

Admin JPM 2 TITLE Determine Actions to Change Containment REVISION 1 Integrity Options During Refueling PROGRAM ILT TIME 15 Minutes DATE:

DEVELOPING Name:

INSTRUCTOR(S): Signature:

REVIEWED AND Program Owner or designee APPROVED BY: Name:

Signature:

Training Supervisor or designee Name:

Signature:

Retention Requirements: Quality Page 1 of 3 1/022404/js/ss

COURSE NUMBER Determine Actions to Change Containment REVISION: 1 AND TITLE: Integrity Options During Refueling REFERENCES 01-OHP-4030-127-041, Refueling Integrity Task:0340260202 Verify Containment Penetration Integrity checks prior to Core Alterations K/A CROSS

REFERENCE:

2.2.26 K/A IMPORTANCE: SRO 3.7 EVALUATION SETTING Classroom/simulator HANDOUTS Task Briefing 01-OHP-4030-127-041 Original Data Sheet 1 CPN-74 pages 113 to 116 01-OHP-4030-127-041 Blank Data Sheet 1 CPN-74 pages 113 to 116 ATTACHMENTS None SIMULATOR SETUP N/A Page 2 of 3

COURSE NUMBER Determine Actions to Change Containment REVISION: 1 AND TITLE: Integrity Options During Refueling TASK OBJECTIVES/STANDARDS Verify alignment of valves during Refueling per 01-OHP-4030-127-041, Refueling Integrity, observing applicable precautions and limitations and procedural steps.

TASK BRIEFING Given the following:

• Unit 1 is in Mode 6

• Core Offload in Progress

• You are the Unit 1 Unit Supervisor Panel 104 Drop 33 CONTAINMENT CTRL AIR HDR PRESSURE LOW and Panel 124 Drop 30 CNTMT 100 PSI CTRL AIR HDR 2 PRESSURE LOW Alarms have annunciated.

MTI has investigated and determined that pressure transmitter 1-XPA-104 has failed.

01-OHP-4030-127-041, Refueling Integrity is impacted by this failure. Option A was previously chosen for CPN-74(1) on Data Sheet 5 (page 306).

The Shift Manager directs you select a different option per 01-OHP-4030-127-041,Step 4.2.6 and Data Sheet 1 for CPN-74 (page 113).

The option Chosen must maintain air to Containment and NOT require a Containment Entry.

Page 3 of 3

COURSE NUMBER Determine Actions to Change Containment Integrity Options During Refueling REVISION: 1 AND TITLE:

General CUES:

Page 1 of 6

COURSE NUMBER Determine Actions to Change Containment Integrity Options During Refueling REVISION: 1 AND TITLE:

CUE : Alarm is no longer valid Page 2 of 6

COURSE NUMBER Determine Actions to Change Containment Integrity Options During Refueling REVISION: 1 AND TITLE:

Alarm is not Valid nor clear Alarm is not Valid nor clear CT: Determines that Option C is required Option Verifies that Air headers are not Crosstied CUE: Proceduralized Temporary Modification Log Index does NOT list Containment Control Air Header crosstie.

Page 3 of 6

COURSE NUMBER Determine Actions to Change Containment Integrity Options During Refueling REVISION: 1 AND TITLE:

CT: Selects one valve and verifies that it cycles Two (2) times Requests that AEO read pressure on 1-XPI-186 at CAS panel Cue : 1-XPI-186 reads 85 psig CT: Verifies Pressure is > 75 psig.

Requests Refuel Tag to be Hung on 1-XPI-186 Cue: Refuel Tag is Hung on 1-XPI-186 Can Not be used as it requires operations inside containment.

Can Not be used as air would be isolated Can Not be used as air would be isolated Page 4 of 6

COURSE NUMBER Determine Actions to Change Containment Integrity Options During Refueling REVISION: 1 AND TITLE:

Evaluators Note: The following signature should be made on the Original copy of 01-OHP-4030-127-041 Data Sheet 1 page 115.

CT: Signs, enters Time & Date that CPN Line (1) was changed Signs that CPN-74 Options are complete on New Copy of 01-OHP-4030-127-041 Data Sheet 1 page 115.

Reports task completed.

JPM IS COMPLETE.

Page 5 of 6

COURSE NUMBER Determine Actions to Change Containment Integrity Options During Refueling REVISION: 1 AND TITLE:

(FOR REFERENCE ONLY)

Page 6 of 6

COURSE NUMBER Determine Actions to Change Containment REVISION: 1 AND TITLE: Integrity Options During Refueling TASK BRIEFING Given the following:

• Unit 1 is in Mode 6

• Core Offload in Progress

• You are the Unit 1 Unit Supervisor Panel 104 Drop 33 CONTAINMENT CTRL AIR HDR PRESSURE LOW and Panel 124 Drop 30 CNTMT 100 PSI CTRL AIR HDR 2 PRESSURE LOW Alarms have annunciated.

MTI has investigated and determined that pressure transmitter 1-XPA-104 has failed.

01-OHP-4030-127-041, Refueling Integrity is impacted by this failure. Option A was previously chosen for CPN-74(1) on Data Sheet 5 (page 306).

The Shift Manager directs you select a different option per 01-OHP-4030-127-041,Step 4.2.6 and Data Sheet 1 for CPN-74 (page 113).

The option Chosen must maintain air to Containment and NOT require a Containment Entry.

Page 1 of 1

Admin JPM 3 TITLE Calculate RCS time to Boil/Core Uncovery - REVISION 0 Loss of RHR PROGRAM NRC License Audit Exam TIME 10 Minutes DATE:

DEVELOPING Name:

INSTRUCTOR: Signature:

OPERATIONS REVIEW: Name:

Signature:

Page 1 of 3

COURSE Calculate RCS time to Boil/Core Uncovery -Loss of RHR REVISION: 1 NUMBER AND TITLE:

REFERENCES 02-OHP-4022-017-001, Rev 13c Loss of RHR Cooling Task Number: ADM0050304 Implement Operations Department Procedures K/A Number: 2.1.25 Ability to obtain and interpret station reference materials such as graphs, monographs, and tables which contain performance data.

K/A IMPORTANCE: RO: 2.8 SRO: 3.1 EVALUATION SETTING Unit 2 Simulator/Classroom HANDOUTS Task Briefing Copy of 02-OHP-4022-017-001, Rev 13c ATTACHMENTS None SIMULATOR SETUP N/A Page 2 of 3

COURSE Calculate RCS time to Boil/Core Uncovery -Loss of RHR REVISION: 1 NUMBER AND TITLE:

Task Objectives/Standards The operator correctly identifies the applicable curves and determines the time to Core Boil and Uncovery Task Briefing You are an extra SRO.

Unit 2 is in a refueling outage and has experienced a loss of RHR. Efforts are underway to restore RHR or some other method of core cooling. The unit was shutdown on July 9, 2004 after operating since January 9, 2004.

The Unit Supervisor directs you to determine the amount of time to Core Boiling and Core Uncovery as per the NOTE prior to Step 15 of 02-OHP-4022-017-001, Loss of RHR Cooling.

The Reactor vessel is currently open to Containment (Vessel Head removed) and RCS temperature is approximately 115°F. RCS water level is at the top of the vessel flange.

Page 3 of 3

COURSE NUMBER Calculate RCS time to Boil/Core Uncovery on a Loss of RHR REVISION: 1 AND TITLE:

Candidate determines that Figure 3 and 4 must be used.

Page 1 of 3 Revision 0

COURSE NUMBER Calculate RCS time to Boil/Core Uncovery on a Loss of RHR REVISION: 1 AND TITLE:

Candidate determines that the plant has been shutdown for 31 days after operating for approximately 182 days.

CT: Candidate reports the calculated Time to Boil is 30 (27.5 to 32.5) minutes.

CUE: Acknowledge the Time to Boil is ___ minutes.

Page 2 of 3 Revision 0

COURSE NUMBER Calculate RCS time to Boil/Core Uncovery on a Loss of RHR REVISION: 1 AND TITLE:

Candidate determines that the plant has been shutdown for 31 days after operating for approximately 182 days.

CT: Candidate reports the calculated Time to Core Uncovery is 220 (210 - 230) minutes from the onset of boiling.

(250 minutes from now - 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> 10 minutes)

CUE: Acknowledge the Time to Core Uncovery is ___

minutes.

Evaluator: JPM IS COMPLETE Page 3 of 3 Revision 0

Task Briefing You are an extra SRO.

Unit 2 is in a refueling outage and has experienced a loss of RHR. Efforts are underway to restore RHR or some other method of core cooling. The unit was shutdown on July 9, 2004 after operating since January 9, 2004.

The Unit Supervisor directs you to determine the amount of time to Core Boiling and Core Uncovery as per the NOTE prior to Step 15 of 02-OHP-4022-017-001, Loss of RHR Cooling.

The Reactor vessel is currently open to Containment (Vessel Head removed) and RCS temperature is approximately 115°F. RCS water level is at the top of the vessel flange.

admin jpm3.doc Page 1 of 1

Admin JPM 4 TITLE Review Liquid Waste Release (Alternate Path) REVISION 0 PROGRAM NRC License Audit Exam TIME 15 Minutes DATE:

DEVELOPING Name:

INSTRUCTOR: Signature:

OPERATIONS REVIEW: Name:

Signature:

Page 1 of 3

COURSE NUMBER Review Liquid Waste Release (Alternate Path) REVISION: 1 AND TITLE:

References 12-OHP-4021-006-004, Rev 27, Transferring Distillate From Monitor Tanks PMP-6010-OSD-001, Rev , Offsite Dose Calculation Manual Task:: 0230140102 Verify releases comply with the Offsite Dose Calculation Manual.

0060220103 Authorize a radioactive liquid release to the Circulating Water System.

K/A CROSS

REFERENCE:

2.3.6 K/A IMPORTANCE: SRO 3.1 RO 2.1 Evaluation Setting Classroom / Simulator Handouts Task Briefing Prepared Release Package:

• 12-OHP-4021-006-004, Transferring Distillate From Monitor Tanks:

• Attachment 3, Monitor Tank Release To The Circ. Water System

• Data Sheets 1, Monitor Tank Release Permit

• Line up Sheet 7, Monitor Tank No. 3 Release Valve Lineup

• Liquid Release Worksheet (1) (sample package)

Available References

• PMP-6010-OSD-001, Offsite Dose Calculation Manual Simulator Setup N/A Page 2 of 3

COURSE NUMBER Review Liquid Waste Release (Alternate Path) REVISION: 1 AND TITLE:

Task Objectives/Standards Identifying conditions that would prevent authorization of a liquid release in accordance with Step 4.5.4 of 12-OHP-4021-006-004, Transferring Distillate From Monitor Tanks.

Task Briefing You are the WCC/SRO.

The following conditions exist:

• Both units are at 100% power

• All Circulating Water Pumps are running in both units

• Both units Circulating Water Systems are in their normal alignment

§ All condenser water box halves are in service

§ Neither unit is in De-Ice Mode

• RRS-1001, Liquid waste Effluent Monitor is INOPERABLE

• Monitor Tank # 3 is ready to be released to the Unit 2 circulating water system.

• The monitor tank release package is ready for your review and authorization.

Perform review and authorize monitor tank release (L-04-15) in accordance with Step 4.5.4 of 12-OHP-4021-006-004, Transferring Distillate From Monitor Tanks.

NOTE: Mark any (and all) conditions that would prevent authorization of this release.

Page 3 of 3

COURSE NUMBER Review Liquid Release (Faulted) REVISION: 1 AND TITLE:

PMP-6010-OSD.001 requires independent verification of lineup and samples with Monitor RRS-1001 inoperable.

Attachment 3.2 Action 1.

CT - Identifies that the discharge alignment was NOT independently verified by two (different) operators for CW (Circ Water) valves located in the Turb Bldg on first page (page 53) of Lineup Sheet 7 (i.e., 1-CW-123, 1-CW-124, 2-CW-123, 2-CW-124).

CT - Identifies that two independent samples were NOT performed as only one LIQUID RELEASE WORKSHEET form is included in the release package.

Identifies that greater than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> has elapsed since chemistry approved the release (Data Sheet 1, Section 2, Chemistry Approval Date/Time (Sample: 2/2/04 @ 0612, Exam: 2/3/04 after 1600)

Cue: If the candidate asks, the current time is as-is (real time).

Cue: Reports task completed.

Evaluator: JPM IS COMPLETE Page 1 of 1

Task Briefing You are the WCC/SRO.

The following conditions exist:

• Both units are at 100% power

• All Circulating Water Pumps are running in both units

• Both units Circulating Water Systems are in their normal alignment

§ All condenser water box halves are in service

§ Neither unit is in De-Ice Mode

• RRS-1001, Liquid waste Effluent Monitor is INOPERABLE

• Monitor Tank # 3 is ready to be released to the Unit 2 circulating water system.

• The monitor tank release package is ready for your review and authorization.

Perform review and authorize monitor tank release (L-04-15) in accordance with Step 4.5.4 of 12-OHP-4021-006-004, Transferring Distillate From Monitor Tanks.

NOTE: Mark any (and all) conditions that would prevent authorization of this release.

admin jpm4.doc Page 1 of 1

Title:

NRC2004-A1a Revision: 0 Emergency Plan Classification with PAR REFERENCES Procedure: PMP-2080-EPP-101 revision 4, Emergency Plan Classification Task: EPP0020703 Classify an Emergency Condition K/A: 2.4.41 Knowledge of the emergency action level thresholds and classifications.

K/A IMPORTANCE: SRO 4.1 RO 2.3 EVALUATION SETTING Classroom or Office HANDOUTS Task Briefing Sheet ATTACHMENTS None SIMULATOR SETUP None

Title:

NRC2004-A1a Revision: 0 Emergency Plan Classification with PAR Task Objectives/Standards In accordance with procedures when an emergency event has occurred or changed, the operator will be able to:

1) Classify an Emergency Condition

2) Develop a Protective Action Recommendation Task Briefing You are the Shift Manager.

A Steam Generator Tube Rupture (SGTR) event with reduced ECCS flow capability has occurred. The crew has transitioned to OHP-4023-E-3, SGTR, and is currently working thier way through the procedure. The PORV on the ruptured Steam Generator opened and failed to re-close 30 minutes ago. Currently no charging pumps are running.

The following plant conditions exist:

! Local actions to start a charging pump are underway but have not been successful

! Local actions to isolate the failed Steam Generator PORV are underway but have not been successful

! Containment pressure is 0.4 psig and stable

! Chemistry reports Primary coolant activity is 325 FCi/cc I-131 dose equivalent

! CETC readings of the five highest temperatures indicate 500EF and stable

! Containment air temperature is 125EF and stable

! MET data indicates no precipitation with the wind from 216E at 5 mph

! The DAP program is not functioning due to a software problem Inform the examiner of the Emergency Classification of this event and any applicable Protective Action Recommendations THIS IS A TIME CRITICAL JPM Record Start Time___________

Title:

NRC2004-A1a Revision: 0 Emergency Plan Classification with PAR Note Simulator Indications are NOT applicable to this JPM Acceptance Criteria CT 1. General Emergency Classification based on Loss of 2 fission Product Barriers and the Potential Loss of Third Barrier.

CT 2. Evaluate and Complete EMD-32a, Nuclear Plant Event Notification. PAR is to Evacuate sectors B, C, & D (Areas 1, 2, and 3) to 5 miles.

CT 3. Complete classification of the event within 15 minutes of the event; complete the EMD-32a form within 5 minutes to allow for Shift Manager review and communicator making notification (5 minutes each).

Title:

NRC2004-A1a Revision: 0 Emergency Plan Classification with PAR Task Briefing You are the Shift Manager.

A Steam Generator Tube Rupture (SGTR) event with reduced ECCS flow capability has occurred. The crew has transitioned to OHP-4023-E-3, SGTR, and is currently working thier way through the procedure. The PORV on the ruptured Steam Generator opened and failed to re-close 30 minutes ago. Currently no charging pumps are running.

The following plant conditions exist:

! Local actions to start a charging pump are underway but have not been successful

! Local actions to isolate the failed Steam Generator PORV are underway but have not been successful

! Containment pressure is 0.4 psig and stable

! Chemistry reports Primary coolant activity is 325 FCi/cc I-131 dose equivalent

! CETC readings of the five highest temperatures indicate 500EF and stable

! Containment air temperature is 125EF and stable

! MET data indicates no precipitation with the wind from 216E at 5 mph

! The DAP program is not functioning due to a software problem